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Simulation Of Irradiation Of A Molten Salt Loop At The Mit Reactor
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Book Synopsis Simulation of Irradiation of a Molten Salt Loop at the MIT Reactor by : Loukas Carayannopoulos
Download or read book Simulation of Irradiation of a Molten Salt Loop at the MIT Reactor written by Loukas Carayannopoulos and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past decade or so, molten salt reactors (MSR) have gained a lot of interest within the nuclear energy community, with two of the ten reactor designs supported by the Department of Energy's (DOE) Advanced Reactor Development Program being MSRs. Commercializing MSR technology requires new experimental facilities to improve understanding of molten salt behavior in reactor-like environments. The Nuclear Energy University Program approved a project to design and build a molten salt test bed that will be irradiated by the MIT Reactor (MITR), which will provide testing capabilities that have not existed since the shutdown of the Molten Salt Reactor Experiment (MSRE) in 1969. The main experimental goals of the project are (1) to build a molten salt loop that operates between 550° C and 700° C and is irradiated by neutrons from the MITR to duplicate conditions in a molten salt reactor, (2) to produce data regarding the transport, diffusion, and dissolution of tritium and radionuclides in molten salts, and (3) to provide a facility for testing chemistry control, salt cleanup, tritium control, and instrumentation. To safely design this facility, an understanding of the radioactivity generated in the loop is needed. The purpose of this work is to model the irradiation of the salt loop, using MCNP and Serpent, to determine the necessary amount of radiation shielding and the activation of different salts proposed for use in MSRs. The salts considered are FLiBe, LiF-BeF[subscript 2]-ZrF[subscript 4]-UF[subscript 4] used in the MSRE, LiF-BeF[subscript 2]-UF[subscript 4] suggested as a fuel salt by Terrestrial Energy and Flibe Energy, LiF-BeF[subscript 2]-ThF[subscript 4] suggested as a blanket salt by Flibe Energy, and NaCl-UCl[subscript 3] suggested as a fuel salt by TerraPower. FLiBe will generate 1.413 ± 0.024 mCi/hr of tritium, with all other fluoride salts generating similar quantities, and a total of 1413 ± 24 Ci over a 1000-hour period -- the maximum continuous operation time proposed for the facility. The maximum radioactivity produced in 1000 hours of operation is 546.9 Ci in the chloride salt. The quantities of tritium and other radioactive products formed in each of the salts make this facility an important tool for the development of MSR technology.
Book Synopsis Global Progress on Molten Salt Reactors by : Thomas James Dolan
Download or read book Global Progress on Molten Salt Reactors written by Thomas James Dolan and published by Elsevier. This book was released on 2024-02-05 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Global Progress on Molten Salt Reactors: A Companion to Dolan’s Molten Salt Reactors and Thorium Energy, Second Edition presents global perspectives on the latest research and technological advances. Each case study utilizes a comprehensive template that guides the reader through country specific research. Useful data which can be applied to work and research is included, along with a list of references for further research. Researchers, professional engineers and policymakers will gain a broad picture of worldwide MSR activity and a deep understanding of how theory and practical guidance is applied in a variety of settings, including budgets, approaches and constraints. Provides a collection of case studies from 23 countries, presenting their latest research and activities on Molten Salt Reactors Based on chapter 26 of the first edition of Dolan’s Molten Salt Reactors and Thorium Energy, this companion title presents expanded and more complete coverage of global activities and research Includes advanced technologies, reactor designs and safety and management strategies
Book Synopsis Status of Molten Salt Reactor Technology by : IAEA
Download or read book Status of Molten Salt Reactor Technology written by IAEA and published by International Atomic Energy Agency. This book was released on 2023-11-27 with total page 319 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written to assist individuals in academia and industry and in relevant regulatory and policy roles, this publication provides a summary of the current knowledge on the status of research, technological developments, reactor designs and experiments in the area of advanced reactors that are fueled or cooled by a molten salt. Identification of challenges and areas where research and development are still required in preparation for commercial deployment gives context to current and planned work. The aim of this publication is to share information on programs and projects on molten salt reactors in Member States which will shape future collaborative efforts.
Book Synopsis Organic Moderator-coolant In-pile Irradiation Loop for the MIT Nuclear Reactor by :
Download or read book Organic Moderator-coolant In-pile Irradiation Loop for the MIT Nuclear Reactor written by and published by . This book was released on 1958 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors by : Lelio Luzzi
Download or read book Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors written by Lelio Luzzi and published by Nova Novinka. This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Multi-Physics Modelling (MPM) is an innovative simulation technique that looks very promising for the employment in the field of nuclear engineering as an integrative analysis support in the design development of current and innovative nuclear reactors. This book presents a Multi-Physics Modelling (MPM) approach to the analysis of nuclear reactor core behaviour, developed to study the coupling between neutronics and thermo-hydrodynamics. Reference is made to the Molten Salt Reactor, one of the innovative nuclear systems under development in the framework of the Generation IV International Forum, but the same methodology can be applied to other reactor systems.
Book Synopsis Molten Salt Reactors and Thorium Energy by : Thomas James Dolan
Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts Covers MSR applications, technical issues, reactor types and reactor designs Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1971-10 with total page 1644 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Irradiation of Santowax OMP in the M.I.T. In-pile Loop... by : Dean T. Morgan
Download or read book The Irradiation of Santowax OMP in the M.I.T. In-pile Loop... written by Dean T. Morgan and published by . This book was released on 1962 with total page 174 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multiphysics simulations of Molten Salt Reactors using the Moltres code by : Mateusz Pater
Download or read book Multiphysics simulations of Molten Salt Reactors using the Moltres code written by Mateusz Pater and published by . This book was released on 2019 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The aim of this paper was to model and simulate Molten Salt Reactor (MSR) specific phenomena, to analyzethem on an example of two different MSR designs, and to assess the accuracy of different codes.Although inherent safety features and interesting nuclear properties of MSRs present a number of poten-tial benefits for the field of nuclear energy production, there is an evident lack of experimental data, provenprototypes, and materials being able to withstand extreme conditions. In order to pave the way for MSRs aconsiderable amount of modeling and engineering work must be done. There are only few numerical tools whichare capable of simulating the complex behavior of such reactors properly. One of these codes, Moltres, is anapplication of MOOSE, a C++ based multiphysics simulation environment, and was utilized extensively in thisproject along with a Monte Carlo code called Serpent.The Serpent code was used to generate group constants for the multigroup diffusion equation solver em-bedded in Moltres, which is coupled with delayed neutron precursor (DNP) and thermal hydraulics equations.Simplified models of the Oak Ridge Nuclear Laboratory's Molten Salt Reactor Experiment (MSRE) and ofSeaborg Technologies' Compact Molten Salt Reactor (CMSR) were created in the Serpent and in Gmsh soft-ware which was used to generate a mesh file for Moltres. Moltres simulations took advantage of a symmetryin the two dimensional geometrical models and included only the nuclear reactor core and the effect of heatremoval in the primary heat exchangers. Phenomena such as DNP transport with the moving fuel and crosssection change with the temperature were duly accounted for.Results for the MSRE case were compared to the original design calculations and a good qualitative anddecent quantitative agreement was found. Some propositions to be included in Seaborg Technologies' reactordesign were produced. Two transients, Unprotected Loss Of Flow and Unprotected Loss Of Heat Sink, werelooked into. The Moltres code proved to be a valuable tool to simulate MSRs. However, many uncertaintiesin the input data and numerous model simplifications caused the results to be only preliminary and requiringmore refinemen.
Book Synopsis Temperature Distributions in the M.I.T. Reactor Irradiation Facilities and a Coolant Impurity Study by : Nathaniel Dew Woodson
Download or read book Temperature Distributions in the M.I.T. Reactor Irradiation Facilities and a Coolant Impurity Study written by Nathaniel Dew Woodson and published by . This book was released on 1965 with total page 138 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of a Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors by : Valentino Di Marcello
Download or read book Development of a Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors written by Valentino Di Marcello and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module by : Adrian Leandro
Download or read book Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module written by Adrian Leandro and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: System analysis codes have a long history of providing best-estimate and conservative safety analysis for both light water and advanced reactor technologies. As interest continues to expand with advanced reactor concepts, system analysis codes will need revisions to accommodate the behavior of these technologies. The codes will also need to be updated to the latest numerical techniques to shorten execution time and increase the accuracy of results. One such tool that already encompasses these techniques is the System Analysis Module (SAM). An advanced reactor concept with recent interest is the Molten Salt Reactor (MSR). This concept is built upon the Molten Salt Reactor Experiment (MSRE), which provided early data and experience. Therefore, the objective of this work is to use legacy MSRE data as a basis of comparison with SAM results.Two MSRE models are developed to evaluate SAM. One model is the SAM MSRE water mockup where experimental data was collected for pressure drop measurements. The other model is the complete MSRE primary loop. The MSRE system model incorporates fluoride salt fuel/coolant with heat transfer in both the core and heat exchanger. Estimates for the core coolant temperature profiles allow this reactor to be evaluated. The primary loop model is also altered for various additional studies, such as simulating varying coolant properties and a loss of flow (LOF) response.The SAM model results for the pressure drop of the water mockup model are within 6% with measurements, which provides confidence that the models geometry is physically accurate over a range of flow rates. Coolant temperatures are also accurate for the primary loop model matching the expected axial change in temperature. Alternative coolant properties from the literature with different actinide content yield similar trends in core temperature profiles. A thermal hydraulic demonstration of a LOF transient shows the importance of coupling SAM thermal hydraulic analysis to neutronics. This coupling is essential for simulating MSR transients with system analysis codes.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1984 with total page 1278 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Department of Commerce. Office of Technical Services Publisher : ISBN 13 : Total Pages :522 pages Book Rating :4.E/5 ( download)
Book Synopsis Keywords Index to U.S. Government Technical Reports (permuted Title Index). by : United States. Department of Commerce. Office of Technical Services
Download or read book Keywords Index to U.S. Government Technical Reports (permuted Title Index). written by United States. Department of Commerce. Office of Technical Services and published by . This book was released on 1962 with total page 522 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Molten-Salt Reactor Program Semiannual Progress Report for Period Ending ... by : Oak Ridge National Laboratory
Download or read book Molten-Salt Reactor Program Semiannual Progress Report for Period Ending ... written by Oak Ridge National Laboratory and published by . This book was released on 1965-02 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Department of Commerce. Office of Technical Services Publisher : ISBN 13 : Total Pages :990 pages Book Rating :4.3/5 (91 download)
Book Synopsis Keywords Index to U.S. Government Technical Reports by : United States. Department of Commerce. Office of Technical Services
Download or read book Keywords Index to U.S. Government Technical Reports written by United States. Department of Commerce. Office of Technical Services and published by . This book was released on 1962 with total page 990 pages. Available in PDF, EPUB and Kindle. Book excerpt:
